Text

Proposed Tech Specs Re Primary Coolant Specific Activity
	ML20211A689
Person / Time
Site:	Farley
Issue date:	09/17/1997
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20211A685	List: ML20211A681; ML20211A689;
References
	NUDOCS 9709240331
	Download: ML20211A689 (22)
	v • d • e

.

I Enclosure 4 I

Technical Specification Pages 9709240331 970917 DR ADOCK 05000348 PDR

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P.EACTOR COOLANT SYSTEM

, 3/4.4.9 SPECIFIC ACTfvf?y LIMITING CONDITION FOR OPERATION 3.4.9 The specific activity of the primary coolant shall be limited to

a. Less than or equal to icrocuriJ per gram DOSE l EQUIVALENT I-131;

b. Less than or equal to 00/ E microcurie per gram.

APPLICABILITY: MODES 1, 2, 3, 4, and 5 ACTION:

MODES 1, 2, and 3* '

h. /$

a. With *?' cific activity of the primary coolant greater than microcurie per gram DOSE EQUIVALENT I-131 for more l l than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Tavg less than 500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With ,the specific activity of the primary coolant greater than 100/E microcurie per gram, be in at least HOT STANDBY with Tavg less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

With Tavg greater than or equal to 500*F.

rn lex-UNIT 1 3/44-2.1 AasamusMT. No. 26r63r4967 447,128

0 PIACTOP COOLANT SYSTEM ACTION: (Continued) _

4 HoDES 1, 2, 3, 4, and 5: g, /7

a. With th specific activity of the primary coolant greater than crocurie per gram DOSE EQUIVALENT I-131 or l greater than 2 0 0 / E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS

~

4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4 t

I FARIrr m - 3/4 4-24 Y

AMENDMENT NO. 25 .$ IO6M 120 i

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o TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM N

TYPE OF MEASUREMENT SAMPLE AND AN% LYSIS MODES IN WHICH SAMPLE g AND ANALYSIS FREOUENCY AND ANALYSIS REQUIRED 1

1. Uross Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 e ,,

w 2. Esotopic Analysis for DOSE 1 per 14 days 1

$QUIVALENT I-131 Concentration 1

3. Radiochemical for j 1 per 6 months

Determination w 1#, 2#, 3#, 4#, 5#

4. Isotopic Analysis for Iodine , a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

} including I-131, I-133, and I-135 whenever the specific _,

)

i activity exceeds O.Ab g U PC1/ gram DOSE EQUIVALENT I-131 or 100/E pCi/ gram, and b) One sample between 2 and g 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a 1, 2, 3 THERMAL POWER change i exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

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Uptil the specific activity of the primary coolant system is restored within its limits.

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Sagple to be taken after a rainimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor O'

was gaet subcritical for 48 hcurs or longer.

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20 30 40 50 60 70 80 90 100 PEPCENT Of* PATED THEPHAL POWER i

i FIGURE 3. 4-1 DOSE EQIII.MALEEL I.-1,11. Pri.ma.r.y Coolant Specif.ic Activity Limit Versus l l Percettt crt RKTED TEERIRL POWER with the Ef"tmary Coalmat Specific-

Activity > W -J' gram Dose Equivalent I-131 l FARLEY-UNIT 1 3/4-4-26 AMENDMENT NO.26y$96 II7128 T T

REACTOR COOLANT SYSTEM BASES 3/4.4.8 CNEKISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady state Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Traraient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.9 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that '

the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits in the event of primary-to-secondary leakage as a result of a steamline break.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than C, /c, g macrocuries/ gram DOSE EQUIVALENT I-131, but within the allowable l lamat shown on Figure 3.4-1, acconvuodates possible iodine spiking phenomenon which may occur following changes in THEFNAL POWER.

FARLEY-UNIT 1 B 3/4 4-5 AMENDMENT NO.4Sy26,63y4967 447y128

e

#EA:t:8 ::cLA_v? sysio<

3/4 4 9 SPEcfr!C Activ!TY

_ LIMITING CONDITION TCR CPERATION 3.4.9 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to microcurie per gr'an DOSE EQUIVALENT Z-131s

b. Less than or equal gi o 100/3 mi:rocurie per gram.

APPLICABILIh HODEs 1, 2, 3, 4 and 5 ACTION: "

MODES 1, 2 and 3*: 0./5 y

a. With th specific activity of the primary coolant greater than Mcrocurie per gram Dost EQUIVALDIT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time intsrvat. or exceeding the limit shown on Figure 3.4-1, be in at least Hof STANDsY with T avg less than 500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the ys ecific activity of the primary coolant greater l than 100/3 microcurie per gram, be in at least NOT STANDBY with Tavy less than 500'T withia 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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With T avy greater than or equal to 500*F.'

FARLEY-UNIT 2 3/4 4-23 AMEN!BWIT No. 106

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. sys;e4 ACT:CN: (Concinuedi MODES 1, 2, 3, 4 and 5:

with the specific activity of the primary coolant greater than O. A' **rocurie per gram o sc sourvxtenT z-131 or gr.ater than 100/a microcuries per gram, perform the sagling and analysis requireswnts of item (a of Table 4.4-4 until the specific t activity of the primary coolant is restored to within its limits. g SURVEILLANCE REQUIRDENTS 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

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rARI.ET-UNIT 2 3/4 4-24 AMIO MENT No. 106

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TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMFLE q AND ANALYSIS PADGRAM TYPE OF ISASUREMDIT SAMPLE AND ANALYSIS MQDES IN WHICH SAMPLE 7 AND ANALYSIS FREQUENCY ANb ANALYSIS REQUIRED E

g 1. Gross Activity Detenmination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 H

w 2. Isotopic Analysis for DOSE 1 per 14 days 1 EQUIVAlmfT I-131 Concentration

3. Radiochesnical for j 1 Per 6 months

1 Deterudnation ,

4. Isotopic Analysis for Iodine al once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if, 25, 38, 45, 58 Incitedlag I-131, 1-133, and 1-135 whenever the specific activity exceema .

g pci/ grant DOSE EQUIVALEst?

1-131 or 100/E pC1/grasa, and s.s N b) One sample between 2 and

1, 2, 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months fellowing a

TNFJWWU. POWER change E exceeding 15 percent of _

(8 the RATED TNEggeM. POWER ,

. within a one hour period.

5 Until the specific activity of the primary coolant systesa is restored within its limits.

E

Sample to be taken af t<:r a minismusa of 2 EFFD and 20 days of FONER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

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DOSE EQUTVAZ. INT Z-131 Primary Coelaat Specific Activity Limit Versus Percent of RATED TNUDEL POWER with the Primary Coolant Specific Activity > / gram Dese Equivalent 1-131 b./[

FARI.EY-UNIT 2 3/4 4-26 MEENDMINT No.'106 1

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- PEAT *0R CtclANT SYSTD4 EASES

_J / 4 . 4 . 8 CMD4ISTRY The limitaticas on Reactor Coolant System chemistry ensure that corrosion of g

the Reactor Coolant system is minimited and reduces the' potential 12e Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the steady state Limits provides adequate corrosion protection to ensure the structqtal integrity of the Reactor Coolant System over the lify of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with containment concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to rest' ore the containsment concentrations to within 1.he 3deady state Limits.

The surveillance requirements provide adequate assurance that concentrations in sucess action. of the limits will be detected in sufficient time to take corrective 3/4.4.9 3FECIFTC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not escoed an appropriately small fraction of Part 100 limits in the event of primary-to-s condary leakage as a result of a steam line break.

O#

The ACTION statement pecnitting PQUER OftRATION to continue for limited time periods with the primary coolant's specific activity greater than l microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, aaa w ates possible iodine spiking phenomenon which may occur following changes in THERMAL PCUER.

m e 4 rARLEY-UNIT 2 a 3/4 4-5 AMextmxNT No.106 S4,94-

4 Revised Tcchnical Specification Pages l

Farley Unit 1 Page 3/4 4-23 Replace l Page 3/4 4 24 Replace Page 3/4 4-25 Replace Page 3/4 4-26 Replace Page B 3/4 4-5 Replace Farley Unit 2 Page 3/4 4 23 Replace Page 3/4 4 24 Replace Page 3/4 4 25 Replace Page 3/4 4-26 Replace Page B 3/4 4-5 keplace i- -- - - -

s.

REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY.

LIMITING CONDITION FOR OPERATION

==

3.4.9 The specific activity of the primary coolant shall be limited tot

a. Less than or equal to 0.15 microcurie per gram DOSE l EQUIVALENT I-131;

b. Less than or equal to 100/5 microcurie per gram.

APPLICABILITY: MODES 1, 2, 3, 4, and 5 ACTION:

MODES 1, 2, and 3*:

a. With the specific activity of the primary coolant greater than 0.15 microcurie per gram DOSE EQUIVALENT I-131 for more l than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Tavg less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With the specific activity of the primary coolant greater than 100/E microcurie per gram, be in at least HOT STANDBY with Tavg less than 500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With Tavg greater than or equal to 500'F.

1 FARLEY-UNIT 1 3/4 4-23 AMENDMENT NO. '

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-! .: REACTOR COOLANT SYSTEM ACTION: (Continued)

MODES-1, 2, 3, 4, and 5:

I l a. With the specific-activity of the primary coolant greater i than 0.15 microcurie per gram DOSE EQUIVALENT I-131 or l greater than 100 / E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the-

specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS I 4.4.9 The specific activity of the primary coolant shall be determined to

! be within the limits by performance of the sampling and analysis program of Table 4.4-4.

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FARLEY-UNIT 1 3/4 4-24 AMENDMENT NO.

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.j TABLE 4.4-4 !

PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE : }

AND ANALYSIS PROGRAM

~

TYPE OF. MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE Q AND ANALYSIS FREOUENCY AND ANALYSIS'REDUIRED j E: .

3 1. Gross' Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 !

4 !

~ 2. Isotopic Analysis for DOSE l' per M days 1 .

EQUIVALENT I-131 Concentration '!

3. Radiochemical for E 1 Per 6 months

1 Determination I w

4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 1#, 2#, 3#. 4#, 5# !

Including I-131, I-133, and I-135 whenever the specific i activity exceeds 0.15 g u", pCi/ gram DOSE EQUIVALENT I-131 or 100/E pCi/ gram, and

'l E b) One sample between 2 and 1, 2, 3 ;

y 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a i o THERMAL POWER change r

$ exceeding 15 percent of

$ the RATED THERMAL POWER !

within a one hour period. ;

O

Until the specific activity of the primary coolant system is restored within its' limits. !

Sample to be taken after a n.inimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor '

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w 1 I I! I Il I I I Ii m 0 I l I ! I l I l l I I l l I I l l l I l I 8 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant specific Activity > 0.15 Ci/ gram Dose Equivalent I-131 l FARLEY-UNIT 1 3/4 4-26 AMENDMENT NO.

REACTOR COOLANT SYSTEM BASES 3/4.4.8 2HEMISTRY The' lindtations on Reactor Coolant System chemistry ensure that corrosion ,

of the Reactor Coolant System is minimized and reduces the potential for

_ Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining the chemistry within the steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up-to the Transient Limits, for the specified limited-time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the, Steady State Limits.

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.9 SPECIFIC ACTIVITY

~

The 1 imitations on.the specific activity of the primary coolant ensure that ;

the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an ~

appropriately small fraction of Part 100 limits in the event of primary-to-secondary leakage as a result of a steamline break.

The ACTION statement permitting POWER OPERATION to continue for limited ;

time periods with the primary coolant's specific activity greater than J 0.15 microcuries/ gram DOSE EQUIVALENT I-131, but within the . allowable l limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes-in THERMAL POWER.

FARLEY-UNIT 1 B 3/4 4-5 AMENDMENT NO.

4 REACTOR COOLANT SYSTEM j 3/4.4.9 SPECIFIC ACT4VITY LIMITING CONDITION FOR OPERATION 3.4.9 The specific activity of the primary coolant shall be limited tot

~

a. .Less than or equal to 0.15 microcurie per gram DOSE l EQUIVALENT I-131;

b. Less than or equal to 100/E microcurie per gram.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*:

a.. With the specific activity of the primary coolant greater than 0.15 microcurie per gram DOSE EQUIVALENT I-131 for more l than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit shown on Figure 3.4-1, be in at least HOT STANDBY with T avg less than 500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the primary coolant greater than 100/E microcurie per gram, be in at least HOT STANDBY with Tavg less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With T avg greater than or equal to 500'F.

FARLEY-UNIT 2 3/4 4-23 AMENDMENT NO.

.9 a

REACTOR COOLANT SYSTEM ACTION: (Continued)

MODES 1, 2, 3, 4 and 5:

a. With the specific activity of the primary coolant greater than 0.15, microcurie per gram DOSE EQUIVALENT I-131 or greater thanl 100/E ndcroCuries per gram, perform the sampling and analysis requirements of item da of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis I program of Table 4.4-4.

l 1-EARLEY-UNIT 2 3/4 4-24 AMENDMENT NO.

n

9 f

TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE y MID ANALYSIS PROGRAM W

t*

M TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE i

7 AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED C

h 1. Gross Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 H

M 2. Isctopic Analysis for DOSE 1 por 14 days l' EQUIVALENT I-131 Concentration

3. Radiochemical for j 1 per 6 months

1 Determination

4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 1#, 2#, 3#, 4#, 5#

Including I-131, 1-133, and 1-135 whenever the specific activity exceeds 0.15 g pCi/ gram DOSE EQUIVALE!rP 1-131 or 100/5 pCi/ gram, and w

b) I, 2, 3

} One sartple between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a f THERMAL POWER change M exceeding 15 percent of

the PATED THERMAL POWER within a one hour period.

Until the specific activity of the primary coolant. system is restored within its limits.

Sample to be taken af ter a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

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-QL I I I II I1 l l I il 1 l l i 8 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERNAL POWER with the Primary Coolant Specific Activity > 0.15 C1/ gram Dose Equivalent I-131 l FARLEY-UNIT 2 3/4 4-26 AMENDMENT NO.

ML20211A689

Text

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